Results 1 to 10 of about 18,296 (224)

Tungsten core accumulation study in EAST plasma with lower tungsten divertor by kinetic impurity transport model

Nuclear Materials and Energy, 2022
Tungsten (W) impurity transport and the corresponding core W accumulation is a critical issue in tokamak with W as plasma facing material. In this work, a kinetic W impurity transport code based on the guiding center approximation is applied for the ...
Yihan Wu, Qingrui Zhou, Chaofeng Sang, Yanjie Zhang, Yilin Wang, Dezhen Wang   +5 more
doaj   +4 more sources

The transport of tungsten impurities induced by the intrinsic carbon during upper-single null discharge on EAST tokamak

Nuclear Materials and Energy, 2020
The transport as well as accumulation of tungsten (W) impurity is one of the critical issues for the W divertor operation. The EAST tokamak with W and graphite divertor targets, provides a good platform for the investigation of W impurity behaviors.
Qingrui Zhou, Chaofeng Sang, Guoliang Xu, Rui Ding, Xuele Zhao, Yilin Wang, Dezhen Wang   +6 more
doaj   +4 more sources

Control of tungsten impurity source and edge transport using different gas injection with full tungsten divertor on EAST

Nuclear Materials and Energy, 2022
Tungsten (W) erosion and edge transport are investigated for EAST L-mode discharges with different gas injection. It is found that W erosion can be suppressed or mitigated by Ne or D2 seeding when divertor detachment is achieved.
R. Ding, G.L. Xu, H. Wang, F. Ding, L. Zhang, Q. Zhang, K.D. Li, J.B. Liu, S. Brezinsek, A. Kirschner, S.X. Wang, B.F. Gao, L.Y. Meng, L. Wang, H. Xie, H. Si, R. Yan, D.H. Zhu, J.L. Chen   +18 more
doaj   +3 more sources

The influence of E× B drift on tungsten target erosion and W impurity transport during neon seeding on EAST

Nuclear Fusion, 2023
Mitigating tungsten (W) wall erosion and core accumulation are vitally important for the steady-state operation of tokamaks. It is well known that drifts have a great impact on the transport of charged particles in the edge region, which could affect W ...
Yilin Wang, Chaofeng Sang, Xuele Zhao, Yihan Wu, Qingrui Zhou, Yanjie Zhang, Dezhen Wang   +6 more
doaj   +2 more sources

Modeling of tungsten impurity transport and distribution in EAST based on multi-fluid and kinetic Monte Carlo simulations

AIP Advances
In recent years, the materials of plasma facing components, such as divertor target plates, domes, and outer walls of tokamaks, such as ASDEX Upgrade, WEST, JET, EAST, and ITER, have been changed from carbon to tungsten because of its lower erosion and ...
Ziyang Wen, YiPing Chen, Ling Zhang
doaj   +2 more sources

Impurity transport simulation in the peripheral plasma in the large helical device with tungsten closed helical divertor

Nuclear Materials and Energy, 2018
Long pulse plasma discharges in the Large Helical Device have been often interrupted by iron dust emission induced by electric arcing on the surface of the vacuum vessel.
M. Shoji, G. Kawamura, S. Masuzaki, T. Morisaki   +3 more
doaj   +2 more sources

Simulation study of the influence of E× B drift on tungsten impurity transport in the scrape-off layer

Nuclear Fusion, 2023
Tungsten (W) is used as the plasma-facing material in the divertor region of future fusion reactors, such as ITER; however, its concentration in the core plasma must be maintained at an extremely low level.
Jin Guo, Yuchen Xu, Shifeng Mao, Minyou Ye   +3 more
doaj   +2 more sources

Coupled IMPGYRO-EDDY simulation of tungsten impurity transport in tokamak geometry

Journal of Nuclear Materials, 2009
Abstract We are developing a Monte Carlo transport code, ‘IMPGYRO’ for high- Z impurities. The code includes most of important process of high- Z impurities: (1) the finite Larmor radius effect in realistic tokamak geometries, (2) Coulomb collision of impurity ions with background ions and (3) multi-step ionization/recombination process.
M. Toma, K. Hoshino, K. Inai, M. Furubayashi, A. Hatayama, K. Ohya   +5 more
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Interpretative modeling of impurity transport and tungsten sources in WEST boundary plasma [PDF]

Nuclear Fusion, 2021
The contamination of core plasma by high-Z impurities, especially tungsten (W), is the main reason of very high level of radiated power in WEST experiments. Intrinsic light impurities, mainly oxygen and carbon, play a dominant role in the sputtering of W on plasma facing components.
G. Ciraolo, S. Di Genova, H. Yang, A. Gallo, N. Fedorczak, H. Bufferand, J.P. Gunn, P. Tamain, R. Guirlet, C. Guillemaut, C. Desgranges, C. Bourdelle, E. Tsitrone, J. Bucalossi, M. Scotto D’Abusco, E. Serre, Y. Marandet, M. Raghunathan, A. Sepetys, J. Romazanov, A. Kirschner, S. Brezinsek, the WEST Team   +22 more
openaire   +5 more sources

Impact of E× B drift on tungsten impurity transport and analysis of its instantaneous response: a particle Monte Carlo simulation

Nuclear Fusion
Tungsten (W), as the primary plasma-facing material in tokamaks, is incompatible with the core plasma. Even extremely low concentrations of W impurities can contaminate the plasma.
Yihan Wu, Chaofeng Sang, Yilin Wang, Chen Zhang, Qingrui Zhou, Yudie He, Dezhen Wang   +6 more
doaj   +2 more sources